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T. Oka,M. Furusawa,K. Sudo,L. Dadiel,N. Sakai,H. Seki,M. Miryala,M. Murakami,T. Nakano,M. Ooizumi,K. Yokoyama,M. Tsujimura 한국초전도저온공학회 2021 초전도와 저온공학 Vol.23 No.3
Nickel (Ni) is a kind of the rare earth resources. Since Ni-containing waste is drained after several plating operations in the factories, the effective recycling technique has been expected to be introduced. An actual magnetic separation technique using HTS bulk magnet generating the strong magnetic field has succeeded in collecting the paramagnetic slurry containing Ni-sulphate coarse crystals which were fabricated from the Ni-plating waste. The Ni compound in the collected slurry was identified as NiSO4/6H2O, showing slight differences in the particle size and magnetic susceptibility between the samples attracted and not-attract to the magnetic pole. This preferential extraction suggests us a novel recycling method of Ni resource because the compound is capable of recycling back to the plating processes as a raw material.
Oka, T.,Furusawa, M.,Sudo, K.,Dadiel, L.,Sakai, N.,Seki, H.,Miryala, M.,Murakami, M.,Nakano, T.,Ooizumi, M.,Yokoyama, K.,Tsujimura, M. The Korean Society of Superconductivity and Cryoge 2021 한국초전도저온공학회논문지 Vol.23 No.3
Nickel (Ni) is a kind of the rare earth resources. Since Ni-containing waste is drained after several plating operations in the factories, the effective recycling technique has been expected to be introduced. An actual magnetic separation technique using HTS bulk magnet generating the strong magnetic field has succeeded in collecting the paramagnetic slurry containing Ni-sulphate coarse crystals which were fabricated from the Ni-plating waste. The Ni compound in the collected slurry was identified as NiSO<sub>4</sub>/6H<sub>2</sub>O, showing slight differences in the particle size and magnetic susceptibility between the samples attracted and not-attract to the magnetic pole. This preferential extraction suggests us a novel recycling method of Ni resource because the compound is capable of recycling back to the plating processes as a raw material.
Extension of the operational regime of the LHD towards a deuterium experiment
Takeiri, Y.,Morisaki, T.,Osakabe, M.,Yokoyama, M.,Sakakibara, S.,Takahashi, H.,Nakamura, Y.,Oishi, T.,Motojima, G.,Murakami, S.,Ito, K.,Ejiri, A.,Imagawa, S.,Inagaki, S.,Isobe, M.,Kubo, S.,Masamune, S IOP 2017 Nuclear fusion. Fusion nucléaire. &n.Illiga Vol.57 No.10
<P>As the finalization of a hydrogen experiment towards the deuterium phase, the exploration of the best performance of hydrogen plasma was intensively performed in the large helical device. High ion and electron temperatures, <I>T</I> <SUB>i</SUB> and <I>T</I> <SUB>e</SUB>, of more than 6 keV were simultaneously achieved by superimposing high-power electron cyclotron resonance heating onneutral beam injection (NBI) heated plasma. Although flattening of the ion temperature profile in the core region was observed during the discharges, one could avoid degradation by increasing the electron density. Another key parameter to present plasma performance is an averaged beta value <img ALIGN='MIDDLE' ALT='$\left\langle \beta \right\rangle $ ' SRC='http://ej.iop.org/images/0029-5515/57/10/102023/nfaa7fc2ieqn001.gif'/>. The high <img ALIGN='MIDDLE' ALT='$\left\langle \beta \right\rangle $ ' SRC='http://ej.iop.org/images/0029-5515/57/10/102023/nfaa7fc2ieqn002.gif'/> regime around 4% was extended to an order of magnitude lower than the earlier collisional regime. Impurity behaviour in hydrogen discharges with NBI heating was also classified with a wide range of edge plasma parameters. The existence of a no impurity accumulation regime, where the high performance plasma is maintained with high power heating >10 MW, was identified. Wide parameter scan experiments suggest that the toroidal rotation and the turbulence are the candidates for expelling impurities from the core region.</P>
Development of the readout system for the K2K SciBar detector
Yoshida, M.,Yamamoto, S.,Murakami, T.,Tanaka, M.,Nakaya, T.,Nishikawa, K.,Joo, K.K.,Kim, B.J.,Kim, J.Y.,Kim, S.B.,Lee, M.J.,Lim, I.T. IEEE 2004 IEEE transactions on nuclear science Vol.51 No.6
Readout electronics for the scintillation bar tracking detector (SciBar) in the K2K neutrino oscillation experiment has been developed. SciBar has 14 336 scintillator bars in total. The deposited energy and timing of particles from neutrino interactions in the scintillator bars are measured by 64-channel multianode photo-multiplier tubes (MAPMTs). Compact custom-designed electronics to record the MAPMT signals were developed, consisting of front-end circuit boards attached to each MAPMT and back-end electronics modules sitting in a VME crate. The front-end circuit board multiplexes pulse-height information from all 64 anodes and generates a fast triggering signal. Two sets of ASICs (IDEAS VA32HDR11 and TA32CG) are employed for these functions. The bias voltages and relay of control signals are also handled on the board. The back-end electronics module controls the front-end board by providing the control, timing, and low-voltage signals. The board also digitizes the multiplexed signal from the front-end. The electronics achieves low noise of less than 0.3 photo-electrons and good linearity up to 300 (150) photo-electrons for MAPMTs at the gain of 5×10<SUP>5</SUP> (10<SUP>6</SUP>).
Simulation of the hybrid and steady state advanced operating modes in ITER
Kessel, C.E.,Giruzzi, G.,Sips, A.C.C.,Budny, R.V.,Artaud, J.F.,Basiuk, V.,Imbeaux, F.,Joffrin, E.,Schneider, M.,Murakami, M.,Luce, T.,St John, Holger,Oikawa, T.,Hayashi, N.,Takizuka, T.,Ozeki, T.,Na, International Atomic Energy Agency 2007 Nuclear fusion Vol.47 No.9
<P>Integrated simulations are performed to establish a physics basis, in conjunction with present tokamak experiments, for the operating modes in the International Thermonuclear Experimental Reactor (ITER). Simulations of the hybrid mode are done using both fixed and free-boundary 1.5D transport evolution codes including CRONOS, ONETWO, TSC/TRANSP, TOPICS and ASTRA. The hybrid operating mode is simulated using the GLF23 and CDBM05 energy transport models. The injected powers are limited to the negative ion neutral beam, ion cyclotron and electron cyclotron heating systems. Several plasma parameters and source parameters are specified for the hybrid cases to provide a comparison of 1.5D core transport modelling assumptions, source physics modelling assumptions, as well as numerous peripheral physics modelling. Initial results indicate that very strict guidelines will need to be imposed on the application of GLF23, for example, to make useful comparisons. Some of the variations among the simulations are due to source models which vary widely among the codes used. In addition, there are a number of peripheral physics models that should be examined, some of which include fusion power production, bootstrap current, treatment of fast particles and treatment of impurities. The hybrid simulations project to fusion gains of 5.6–8.3, β<SUB>N</SUB> values of 2.1–2.6 and fusion powers ranging from 350 to 500 MW, under the assumptions outlined in section 3. Simulations of the steady state operating mode are done with the same 1.5D transport evolution codes cited above, except the ASTRA code. In these cases the energy transport model is more difficult to prescribe, so that energy confinement models will range from theory based to empirically based. The injected powers include the same sources as used for the hybrid with the possible addition of lower hybrid. The simulations of the steady state mode project to fusion gains of 3.5–7, β<SUB>N</SUB> values of 2.3–3.0 and fusion powers of 290 to 415 MW, under the assumptions described in section 4. These simulations will be presented and compared with particular focus on the resulting temperature profiles, source profiles and peripheral physics profiles. The steady state simulations are at an early stage and are focused on developing a range of safety factor profiles with 100% non-inductive current.</P>